IP 71111.08

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https://www.nrc.gov/docs/ML1805/ML18051A681.pdf

Inspection Procedure
IP 71111, Reactor Safety-Initiating Events, Mitigating Systems, Barrier Integrity

NRC Inspection Procedures - IP 71111.08

IP 37060, 10 CFR 50.69 Risk-Informed Category and Treatment of Structures, Systems, and Components 10 CFR 50.69 Risk-Informed Category and Treatment of Structures
IP 43004
IP 60853
IP 60854 (1)
IP 60855 (1) Operation of an Independent Spent Fuel Storage Installation
IP 60857, Review of 10 CFR 72.48 Evaluations Review of 10 CFR 72.48 Evaluations
IP 60858, Away-From-Reactor Independent Spent Fuel Storage Installation Inspection Guidance Away-From-Reactor Independent Spent Fuel Storage Installation Inspection Guidance
IP 71002, License Renewal Inspection License Renewal Inspection
IP 71003
IP 71004

IP 71111 (27) Reactor Safety-Initiating Events
IP 71114 (7) Reactor Safety Emergency Preparedness
IP 71124 (8) Radiation Safety-Public and Occupational
IP 71130 (10) Security
IP 71150
IP 71151
IP 71152, Problem Identification and Resolution (PI&R) Problem Identification and Resolution (PI&R)
IP 71152A
IP 71152S, Semiannual Trend Review Semiannual Trend Review
IP 71153, Event Followup Event Followup

IP 92702
IP 92709
IP 92722
IP 92723
IP 93800
IP 93812
IP 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs
IP 95002
IP 95003
TI 2201/004

TI 2515/177
TI 2515/183
TI 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication, Staffing, Multi-Unit Dose Assessment Plans Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication
TI 2515/192
TI 2515/193, Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
TI 2515/194
TI 2515/76
TI 2800/041

IP 71111, Reactor Safety-Initiating Events, Mitigating Systems, Barrier Integrity

Inspection Reports
[list of inspection reports]

	Site	Start date
IR 05000237/2024004	Dresden	10 February 2025
IR 05000382/2023004	Waterford	27 September 2024
IR 05000341/2024002	Fermi	14 August 2024
IR 05000390/2022003	Watts Bar	9 May 2023
IR 05000390/2022002	Watts Bar	12 August 2022
IR 05000390/2021003	Watts Bar	10 November 2021
IR 05000220/2021002	Nine Mile Point	10 August 2021
IR 05000400/2019004	Harris	6 February 2020
IR 05000482/2019004	Wolf Creek	3 February 2020
IR 05000255/2019004	Palisades	28 January 2020

Findings
[list of findings]

	Quarter	Site	Title
05000287/FIN-2018002-01	2018Q2	Oconee	Failure to Perform ISI General Visual Examinations of Containment Moisture Barrier Associated with Containment Liner Leak Chase Test Connection Piping
05000416/FIN-2018002-02	2018Q2	Grand Gulf	Failure to Follow ASME Requirements for Maintaining Inservice Inspection (ISI) Cycles and Perform ASME Required Inservice Inspections within the Scheduled ISI Cycle
05000272/FIN-2017004-01	2017Q4	Salem	Non-conformance with the Containment Thermal Insulation System was not Identified and Corrected
05000275/FIN-2017002-01	2017Q2	Diablo Canyon	Inadequate Expansion Scope of Risk - Informed Welds
05000446/FIN-2017002-02	2017Q2	Comanche Peak	Inadequate Operability Evaluation for Safety - related Pipe Supports
05000250/FIN-2017002-01	2017Q2	Turkey Point	Failure to Perform 100 Percent General Visual Examinations of Containment Moisture Barriers Associated with Containment Liner Leak Chase Test Connections
05000373/FIN-2017001-01	2017Q1	LaSalle	nadequate Controls for ASME Code VT 3 Internal Examination of Pumps and Valves
05000282/FIN-2016004-01	2016Q4	Prairie Island	Baffle Former Bolting Acceptance Criteria
05000456/FIN-2016004-01	2016Q4	Braidwood	Inadequate Control of Welding During FW System Pipe Replacement
05000321/FIN-2016010-01	2016Q2	Hatch	Inaccurate Information Provided Regarding N2E Nozzle Weld Overlay

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NRC Inspection Procedure